Development of FBR piping bellows joints in Japan

Generation IV Reactors Integrated Materials Technology Program Plan: Focus on Very High Temperature Reactor Materials

“…The Japanese have developed design-by-analysis procedures that would replace some of the more onerous aspects of N-290. 42 A draft code case developed in the 1980s for design of nickel-base Alloy 617 components to 982°C is directly pertinent to NGNP and other Gen IV systems with veryhigh-temperature components. 43 The case was approved by ASME Subsection NH and submitted to its parent group, the Subcommittee on Design, for approval.…”